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检索条件"机构=Science and Technology on Reactor system Design Technology Laboratory"
1301 条 记 录,以下是91-100 订阅
Research on Imputation Method for Missing Values of Nuclear Power Plants' Operation Data  13
Research on Imputation Method for Missing Values of Nuclear ...
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13th International Conference on Electronics, Communications and Networks, CECNet 2023
作者: Liu, Jie Qi, Xiaodi Wu, Zhiqiang Jiang, Wei Chen, Zhi Jian, Yifan Wen, Juan School of Computer/Software University of South China China Laboratory of Nuclear Reactor System Design Technology China Nuclear Power Research and Design Institute China
The collection of nuclear power plants operating data is the basis for subsequent fault diagnosis and obtaining the operating status of nuclear power plants, but equipment failures and external interference will lead ... 详细信息
来源: 评论
POST-HOC INTERPRETABILITY BASED PARAMETER SELECTION FOR DATA ORIENTED NUCLEAR reactor ACCIDENT DIAGNOSIS system  29
POST-HOC INTERPRETABILITY BASED PARAMETER SELECTION FOR DATA...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Li, Chengyuan Li, Meifu Qiu, Zhifang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
During applying data-oriented diagnosis systems to distinguishing the type of and evaluating the severity of nuclear power plant initial events, it is of vital importance to decide which parameters to be used as the s... 详细信息
来源: 评论
EMC PERFORMANCE OF DIFFERENT CABLE ROUTING STYLES FOR I&C systemS OF NPPS  29
EMC PERFORMANCE OF DIFFERENT CABLE ROUTING STYLES FOR I&C SY...
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2022 29th International Conference on Nuclear Engineering, ICONE 2022
作者: Yang, Youwei Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
In the nuclear power plants, cables are signal transport links between separated signal processes that must be allowed to communicate with one another in a specified manner. Nowadays, for the instrumentation and contr... 详细信息
来源: 评论
Application of Optimal design in Nuclear Safety-Class DCS design  6th
Application of Optimal Design in Nuclear Safety-Class DCS De...
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6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021
作者: Zhang, Xu Yao, Zhang Chen, Shi-Yong Peng, Hao Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
In the design process of nuclear safety-class digital control system (DCS), there may be mistakes in the details of various drawings for the large number of drawings and heavy design task. In safety-class DCS, with th... 详细信息
来源: 评论
Nuclear Safety-Class DCS Hardware Logic Implementation Scheme Based on Modularization design  6th
Nuclear Safety-Class DCS Hardware Logic Implementation Schem...
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6th International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plant, ISNPP 2021
作者: Hu, Yan-Liang Zhang, Xu Chen, Shi-Yong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
At present, nuclear safety-class DCS can deal with the common cause failure of digital control system software system by building hardware logic control circuit. Different from the digital control system, the hardware... 详细信息
来源: 评论
Phase-Field Modelling of Void Evolution in Binary Alloys Under Irradiation
Phase-Field Modelling of Void Evolution in Binary Alloys Und...
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International Conference on Water reactor Fuel Performance Meeting, WRFPM 2023
作者: Lu, Yong Yang, Yuhang Li, Wenjie Sun, Dan Liu, Xingjun Wang, Cuiping College of Materials and Fujian Key Laboratory of Surface and Interface Engineering for High Performance Materials Fujian Xiamen China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China
The formation and growth of voids have significant influence on the dimensional changes of nuclear materials subjected to irradiation. In this paper, we developed a phase-field model to investigate the evolution of vo... 详细信息
来源: 评论
Experimental Study on Startup Characteristics of Sodium Heat Pipe with Large Length-diameter Ratio  12
Experimental Study on Startup Characteristics of Sodium Heat...
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12th Academic Conference of Geology Resource Management and Sustainable Development, GRMSD 2024
作者: Li, Wenjun Zhang, Zhuohua Su, Dongchuan Wu, Ge Tang, Qizhong Wu, Junjie College of Chemical Safety North China Institute of Science and Technology Hebei Sanhe065201 China Key Laboratory of Nuclear Reactor System Design Technology Nuclear Power Research and Design Institute of China Sichuan Chengdu610213 China
Underground in-situ pyrolysis of oil-rich coal can extract oil and gas resources in coal, which is an important measure for clean and low-carbon utilization of coal resources. The efficiency and energy consumption of ... 详细信息
来源: 评论
design of Static Semantic Analyzer for Code Generator Applied in Safety-Level I&C of NPPs  7th
Design of Static Semantic Analyzer for Code Generator Applie...
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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023
作者: Lan, Lin Wang, Gang Tu, Jun Li, Zhe Huang, Di Zhang, Jia-Cheng Jiang, Wei Nuclear Power Institute of China Institute of Reactor Operation and Application Leshan Beijing China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of the China Chengdu Sichuan China
In the nuclear safety level I&C (Instrument and Control) area, the code generator plays an important role in developing the application software. The main function of the code generator is to translate the Lustre ... 详细信息
来源: 评论
Computational fluid dynamics simulations of spray tests in a multicompartment construction with an Eulerian–Lagrangian approach
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Frontiers in Energy Research 2024年 12卷
作者: Lu, Yazhe Ran, Xu Wei, Zonglan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China
This paper is an investigation of the gas mixing and depressurization effects of containment spray on hydrogen risk during a typical severe accident in a light water reactor (LWR). Two spray tests (ST3_0 and ST3_1) we... 详细信息
来源: 评论
Deep Learning Based Fault Diagnosis for Chemical Process with Statistical Feature Fusion  42
Deep Learning Based Fault Diagnosis for Chemical Process wit...
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42nd Chinese Control Conference, CCC 2023
作者: Zhang, Lei Xia, Hao Cha, Bao School of Control Science and Control Engineering Dalian University of Technology Dalian116024 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610091 China
The existing fault diagnosis methods based on deep neural networks mostly rely on process data for fault classification and diagnosis, which makes it difficult to distinguish minor faults with similar data features. T... 详细信息
来源: 评论